W3P85-1432, Forwards marked-up Page 14.2-136 of Fsar,Reflecting Change to Test Subsection 14.2.12.3.31, Control Sys Checkout, to Delete Step & Ramp Unit Load Changes at 50% Power
| ML20126L160 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/29/1985 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| W3P85-1432, NUDOCS 8507310086 | |
| Download: ML20126L160 (2) | |
Text
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. (so4)see-es4s U0USNSYs July 29, 1985 W3P85-1432 A4.05 Director of Nuclear Reactor Regulation Attention:
Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Knighton:
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 INITIAL TEST PROGRAM
Reference:
Waterford 3 FSAR, Chapter 14 This submittal is made in accordance with 10CFR50.59(b) and the license condition in Section 2.C.10 of the subject license.
Reported herewith is a change made to the Waterford 3 Initial Test Program, as described in reference 1, as amended through Amendment No. 36.
The attached marked-up page 14.2-136 (Amendment 18) of the Waterford 3 FSAR reflects the change made in test subsection 14.2.12.3.31, Control Systems Checkout. The change indicated by this transmittal is the deletion of step and ramp unit load changes at 50% power. This change to the initial test program does not involve a change in the license technient srecifications or an unroviewed safety question. The control systems described in this tent are not safety related and no credit for their operation is taken in any of the Waterford 3 FSAR Chapter 15 analyses.
LP&L has conducted and documented the required 10CFR50.59 safety evaluation.
LP&L will provide the FSAR change in accordance with 10CFR50.71(e) requirements. The original plus 39 copics of this report transmittal are provided in accordance with 10CFR50.59(h).
Very truly yours,
&Y K.W. Cook Nuclear Support & Licensing Manager KWCICFW sms Attachnent cct R.D. Mart in. D.M. Crutchf fold, J.II. Wilnon, NRC Realdent inspectors Offico, INPO Records Centor (J.T. Wheolock), B.W. Churchill, W.M. Stevenson
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WSES-FSAR-UNIT-3 14.2.12.3.31 CONTROL SYSTEMS CHECKOUT 15 14.2.12.3.31.1 Objective 8
15 To demonstrat'e that various control systems operate satisfactorily during steady-state and transient conditions.
14.2.12.3.31.2 Prerequisites 8
A.
The Reactor Regulating System (RRS), Feedwater. Control System' h
(FWCS)', Steam Bypass Control System (SBCS), g: ::: D:::nd S ::::
15 OOC, Pressurizer Level and Pressure Control System, Hotwell Level Control System, and Boration/ Dilution Systems are in operation or are operable.
B.
The plant is operating at the applicable power level (
50, 80 and @
100 percent).
8 14.2.12.3.31.3 Test Method A.
Monitor control systems' performance during steady-state operation (jM(, 50, 80, and 100 percent), and following selected plant trips.
B.
Monitor control systems' performance during d((([f ramp unit load g 15 changes 7, d 'g 100 percent).
Dr., /
g3 3 C.
Initiate control system transients on selected control systems, and monitorsystemresponse(K,50,80,and100 percent).
h 18 14.2.12.3.31.4 Acceptance Criteria l0 A.
The control system gsaintain reactor power, Reactor Coolant System h
(RCS) temperature 3 pressurizer pressure and level, a-d bea^a coa-centr 2 tier within acceptable ranges during both steady-state and transient operation.
15 B.
The control systems maintain the steam generator levels and pres-sures, turbine generator load, and hotwell level within acceptable ranges during both steady-state and transient operation.
NOTES:
Change notification made by LP&L letter W3P85-1263 dated 5/10/85.
h Change notification made by LP&L letter W3P85-1290 dated 5/17/85.
h Denotes the change by this transmittal (W3P85-1432).
LP&L W-3 RECORDS UNCONTROL_ED COPY J
CO NOT USE IN e NY SAFE 1 Y -RELATED TEST!NG.
MAINTEN ANCE. OF. OFEHATiONAL ACTIVITY l
14.2-136 Amendment No.18, (5/81) t a
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